*QNUM 01*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL R*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 000062K303*QUESTIONAll AC power has been lost and equipment is being placed in PULLOUT per ECA-0.0, LOSSOF ALL AC POWER. Which pump will be kept available, and why?

a. One RHR pump, to provide RCS inventory makeup.

b. One SI pump, to provide RCS inventory makeup.

c. One service water pump, to provide Diesel Generator cooling.

d. One charging pump, to provide RCP seal cooling.*ANSWERC*REFERENCEECA-0.0, CAUTION prior to step 6INPO Exam Bank, BYRON1 10/29/2001 ExamBankHigher

*QNUM 02*HNUM*ANUM*QCHANGED FALSE*ACHANGED FALSE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL R*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 059000K408*QUESTIONThe controller output which automatically positions the Main Feedwater Regulating Valves (FW-7A & B) to maintain programmed level uses steam generator narrow range water level ANDwhich of the following?

a. The setpoint established by the operator on the control station

b. Steam flow and feedwater flow

c. Steam flow, feedwater flow and Turbine impulse pressure

d. Turbine impulse pressure*ANSWERB*REFERENCESLESSON PLAN RO2-02-LP05A, MAIN FEEDWATERSYSTEM DESCRIPTION 05A, FEEDWATERNewHigher

*QNUM 03*HNUM*ANUM*QCHANGED TRUE*ACHANGED FALSE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL R*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 022000K302*QUESTIONContainment temperature has increased from 100 degrees F to 160 degrees F due to acontainment cooling malfunction. If the plant is stable at 100% power and there are negligibleRCS or containment pressure changes, which one of the following describes the effect of theincrease in containment temperature on the pressurizer level indicated by the pressurizer levelcontrol channels?

a. Indicated level will be HIGHER than actual level because the reference leg fluiddensity decreases.

b. Indicated level will be LOWER than actual level because the reference leg fluiddensity decreases.

c. Indicated level will be HIGHER than actual level because the elevatedcontainment temperature causes increased flashing in the reference leg.

d. Indicated level will be LOWER than actual level because of the elevatedcontainment temperature causes increased flashing in the reference leg.

*ANSWERA*REFERENCENRC Exam Bank, Kewaunee 02/21/1994 ExamADV-SYS-LP-36D, p. 11ADV-SYS-LP-36D, EO-RO4.aBankHigher

*QNUM 04*HNUM*ANUM*QCHANGED FALSE*ACHANGED FALSE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL R*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 056000K103*QUESTIONBoth Main Feedwater pumps are running when the “A” Main Feedwater pump trips. WHICHONE (1) of the following conditions prevents the start AND continued operation of the “A” MainFeedwater pump?

a. Lube oil pressure is 10 psig.

b. Suction pressure is 210 psig.

c. Recirculation valve is FULL open.

d. Only one Condensate pump is running.*ANSWERD*REFERENCENRC Exam Bank, Prairie Island 1 & 2 05/09/1994 ExamModifiedMemory

*QNUM 05*HNUM*ANUM*QCHANGED FALSE*ACHANGED FALSE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL R*EXMNR K. Walton*QVAL 1.00*SEC*SUBSORT*KA 011000K202*QUESTIONWith power to 480 volt Bus 1-43 deenergized, which pressurizer heaters would be affected?

A. Backup group 1B ONLY

B. Backup groups 1D AND 1E ONLY

C. Backup Group 1A ONLY with transfer switch in Normal

D. Backup group 1A with transfer switch in Alternate AND control group 1C ONLY*ANSWERB*REFERENCESE-240 Rev. AQAdv System LP Objective R02-05-LP36D.003 (“N/A’)NewMemory

*QNUM 06*HNUM*ANUM*QCHANGED TRUE*ACHANGED FALSE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL R*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 079000K101*QUESTIONGiven the following:

- Station and Instrument Air System is in a normal/automatic system lineup.- The station air compressor preferred selector switch is aligned to Compressor G.

Which of the following automatically occur when the Station and Instrument Air System airheader pressure is decreasing and reaches 95 psig?

a. Air dryers are bypassed AND Station air compressor F starts.

b. Station air compressor F starts AND SA-400, (SA Header B Supply Valve) is fullyclosed.

c. SA-200, (SA Header A Supply Valve) AND SA-400, (SA Header B Supply Valve)start to close.

d. Instrument air compressor C starts and isolates from station air header ANDSA-200, (SA Header A Supply Valve) is fully closed.

*ANSWERC*REFERENCEKNPP SD 1, Rev 1, p 6; LP O-RO-LP-2.11.1, EO 3NRC Exam Bank, Kewaunee 1993 ExamModifiedHigher

*QNUM 07*HNUM*ANUM*QCHANGED TRUE*ACHANGED FALSE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL R*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 015000K101*QUESTIONWith the plant initially at 100% power, steady-state, which one of the following describes aneffect of power range channel N-42 upper detector failing HIGH?

a. Reactor trips on high flux.

b. Main feed regulating valves fully open.

c. Control rods step out to high bank rod stop.

d. Over-temperature DT setpoint for one channel decreases.*ANSWERD*REFERENCENRC Exam Bank, V. C. Summer 1 1992/05/18 ExamBankHigher

*QNUM 08*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL R*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 000065K304*QUESTIONThe unit is at 100% power with Instrument air pressure at 115 psig. Station Air Compressor Fis tagged out for preventive maintenance. What will instrument air pressure do when StationAir Compressor G is tripped.

a. decrease, then increase to a value above its previous pressure.

b. remain unaffected.

c. slowly decrease to a point where the unit will have to be tripped.

d. decrease, then increase to a value below its previous pressure.*ANSWERD*REFERENCENRC Exam Bank, North Anna 1 01/26/1996 ExamBankHigher

*QNUM 09*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL R*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 000003K103*QUESTIONThe following plant conditions exist:

- Reactor is Critical at 10E-3 percent power- RCS Tavg is 547 deg F and steady- Pressurizer pressure is 2235 psig and steady- Control Bank D position is 100 steps- ONE Control Bank D rod drops

Describe the INITIAL response of Tavg and Pressurizer pressure (PZR Press):

Tavg PZR Press

a. Remain the same Remain the same

b. Increase Remain the same

c. Remain the same Increase

d. Decrease Decrease*ANSWERA*REFERENCENRC Exam Bank, Prairie Island 1 & 2 09/28/1992 ExamBankHigher

*QNUM 010*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL R*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 000027K203*QUESTIONThe following conditions exist:

- 90% Reactor power.- Pressurizer Pressure control is in automatic- Backup heaters are in "AUTO".- Actual Pressurizer Pressure is 2235 psig.

The Pressurizer Pressure Master Controller malfunctions and its SETPOINT drifts to 2100 psigover a 10 minute period. Which of the following describes the INITIAL automatic response ofthe Pressurizer Pressure Control System as this failure occurs?

a. Spray valves throttle closed and variable heaters go to maximum current.

b. Spray valves throttle open and variable heaters go to minimum current.

c. Pressurizer PORVs PR-2A and PR-2B open, Spray valves throttle open, andGroup ‘C’ heaters go to minimum current.

d. Spray valves throttle closed, pressurizer backup heater groups go to maximumcurrent, and backup heaters come “ON”.

*ANSWERB*REFERENCEINPO Exam Bank, BYRON1 10/29/2001 ExamModifiedHigher

*QNUM 011*HNUM*ANUM*QCHANGED TRUE*ACHANGED FALSE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL R*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 006000 2.3.11*QUESTIONWhich of the following electrical interlocks prevents release of radioactive water to the RWSTduring transfer to Containment Sump Recirculation during a LOCA?

a. Close SI-300A/B, RWST Supply Valve to an RHR pump, before opening SI-350A/B, Containment Sump B Isolation Valve to an RHR pump.

b. Close SI-208 or SI-209 SI Recirculation Isolation Valves before opening SI-350A/B and 351A/B, Containment Sump B Isolation Valves to an RHR pump.

c. Close SI-208 or SI-209 SI Recirculation Isolation Valves before opening RHR-299A/B RHR Heat Exchanger Outlet Valve to an SI pump.

d. Open SI-350A/B and 351A/B, Containment Sump B Isolation Valves beforeopening RHR-299A/B RHR Heat Exchanger Outlet Valve to an SI pump.

*ANSWERB*REFERENCESES-1.3, Transfer to Containment Sump RecirculationSystem Description 33, Safety Injection SystemNewMemory

*QNUM 012*HNUM*ANUM*QCHANGED FALSE*ACHANGED FALSE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL R*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 008000A308*QUESTIONGiven the following conditions:

- Component Cooling Pump "A" is running- Component Cooling Pump "B" is in standby- D/G "B" is out of service for maintenance

A safety Injection signal is generated. Which one of the following describes the response of theComponent Cooling Water Pumps?

Pump A Pump B

a. Runs continuously Sequences on

b. Stops then sequences on Remains off

c. Runs continuously Remains off

d. Stops then sequences on Sequences on*ANSWERA*REFERENCEKewaunee Exam Bank QuestionLesson Plan Objective RO2-01-LP31.004CCW System Description 31BankHigher

*QNUM 013*HNUM*ANUM*QCHANGED FALSE*ACHANGED FALSE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL R*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 003000A304*QUESTIONGiven the following conditions:

- The plant is operating at 18% power- The high pressure piping to RCS flow instrument FT-411 on Loop A breaks

What is the status of Loop A RCS flow indicators and what is the resulting plant condition(assume NO operator action is taken)?

a. All Loop A flow indicators will read low, and the reactor will trip on RCS loop lowflow.

b. All Loop A flow indicators will read low, and the reactor will trip on low PRZRpressure.

c. Only FI-411 RCS flow indication will read low, and no reactor trip is generated.

d. Only FI-411 RCS flow indication will read low, and the reactor will trip on lowPRZR pressure.

*ANSWERA*REFERENCELESSON PLAN RO2-02-LP362,SYSTEM DESCRIPTION 36, RCSKewaunee 12/2000 ExamBankHigher

*QNUM 014*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL R*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 061000K101*QUESTIONGiven the following conditions:

- The plant is at 15% power- S/G ‘B’ level channel LT-473 is removed from service per A-MI-87

If S/G ‘B’ level channel LT-471 fails high, what would be the status of feed for the S/Gs?

a. Both S/Gs are being fed from the motor-driven AFW Pumps only.

b. Both S/Gs are being fed from the turbine-driven AFW Pump only.

c. S/G A is being fed from the motor-driven AFW Pump. S/G B has no feed flow.

d. Feed to S/G A remains normal. Feed to S/G B lowers due to throttling close ofFW-7B, S/G B Main Feed valve.

*ANSWERA*REFERENCESystem description 05A, Feedwater SystemSystem description 05B, Auxiliary Feedwater SystemKewaunee Exam BankBankHigher

*QNUM 015*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL R*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 004000A405*QUESTIONWhich one of the following describes the operation of LD-13, Letdown Line Pressure ReliefValve?

a. Relieves at 200 psig to the VCT

b. Relieves at 150 psig to the PRT

c. Relieves at 150 psig to the VCT

d. Relieves at 200 psig to the PRT.*ANSWERA*REFERENCEINPO Exam Bank - Kewaunee Exam 12/18/1997System Description 35, CVCSBankMemory

*QNUM 016*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL R*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 061000A101*QUESTIONThe plant is in Hot shutdown, with the following conditions:

- Tave = 547 deg F with both RXCPs operating� A Main Feedwater Pump is running- Steam Generator A Narrow Range Level = 20%- Steam Generator B Narrow Range Level = 15%- Condensate Pump A is Hold Carded in Pullout.- Condensate Pump B is running- All three Auxiliary Feedwater Pumps are in Off and in Pullout- All the support conditions for the Auxiliary Feedwater Pumps are met

At the direction of the CRS, the BOP places all three Auxiliary Feedwater Pump controlswitches into the AUTO position.

Without further operator actions, what is the status of the Auxiliary Feedwater Pumps?

MDAFW Pumps TDAFW

a. Running Running

b. Running Off

c. Off Running

d. Off Off*ANSWERB*REFERENCELesson Plan RO2-05-LP05B, Aux FeedwaterKewaunee Exam BankBankHigher

*QNUM 017*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL R*EXMNR K Walton*QVAL 1.00*SEC*SUBSORT*KA 045A401*QUESTIONSP-54-086, “Turbine Stop and Governor Valve Operability,” directs depressing the CLOSE SV-1 pushbutton. Which of the following statements identifies an expected response of theturbine control valves (CV-1 through CV-4) and turbine stop valve (SV-1) to this action?

a. SV-1 closes, then CV-1 and CV-3 close.

b. SV-1 closes, then CV-1 and CV-2 close.

c. CV-1 and CV-2 close, then SV-1 closes.

d. CV-1 and CV-3 close, then SV-1 closes.*ANSWERD*REFERENCESP-54-086, “Turbine Stop and Governor Valve Operability Test,” Pg 3 of 17.NewMemory

*QNUM 018*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL R*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 2.1.25*QUESTIONThe following conditions exist:

- A LOCA has occurred.- The crew is trying to reduce ECCS flow.- All equipment is operating properly.- Wide Range RCS pressure is 800 psig.- 65 deg F of subcooling is required to stop one of the ECCS pumps.

What is the MAXIMUM Core Exit Thermocouple temperature at which the pump is stopped?

a. 430 deg F.

b. 455 deg F.

c. 480 deg F.

d. 505 deg F.*ANSWERB*REFERENCEINPO Exam Bank, Byron - 10/29/2001 ExamBankHigher

*QNUM 019*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL R*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 2.1.11*QUESTIONGiven the following:

- The reactor is critical at 1% power.- SI Accumulator “A” water volume was just found to be 1270 cubic ft (48%).- SI Accumulator “B” water volume was found to be 1220 cubic ft (20%) at the

same time.

What action is required due to these conditions, if any?

a. No action is needed due to these conditions.

b. SI Accumulator “A” water volume must be restored to limits.

c. SI Accumulator “B” water volume must be restored to limits.

d. Action must be initiated within 1 hour to go to HOT SHUTDOWN.

*ANSWERC*REFERENCELesson Plan R02-05-LP-033TS 3.3.a. AccumulatorsNewHigher

*QNUM 020*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL R*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 2.2.27*QUESTIONGiven the following conditions:

- Reactor Vessel Head AND Upper Internals have been removed.- Residual Heat Removal boron concentration is 2458 ppm.- The reactor has been shutdown for 7 days.- Spent Fuel Pool Pump “A” is operating per N-SFP-21, Spent Fuel Pool Cooling

and Cleanup System. Spent Fuel Pool Pump “B” is inoperable.- Residual Heat Removal Pump “A” is operating. Residual Heat Removal Pump

“B” is inoperable.- Refueling Cavity level is greater than 23 feet above the vessel flange.

Based on the plant status given, determine what condition must be resolved to meetrequirements for a fuel shuffle within the reactor that is NOT a full core offload.

a. Residual Heat Removal boron concentration is too low.

b. Spent Fuel Pool Cooling Pump “B” is required to be operable.

c. The reactor has not been shutdown long enough.

d. Residual Heat Removal Pump “B” is required to be operable.*ANSWERA*REFERENCELesson Plan R02-05-LP-053N-FH-53-CLC, Pre-Refueling ChecklistRF-01.00, KNPP Refueling ProcedureNewHigher

*QNUM 021*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL R*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 2.2.26*QUESTIONWhich of the following is the purpose of NAD-02.07, Kewaunee Refueling Operations?

a. Provides step-by-step instructions to be used by fuel handlers during coreoffload.

b. Provides administrative instructions for reactor engineers to follow whendeveloping the fuel shuffle sequence to prevent inadvertent criticality during corereload.

c. Describes the organization and responsibilities for reactor vessel disassembly,reassembly, and fuel handling operations.

d. Provides step-by-step instructions on completing a Fuel Assembly HandlingDeviation Report.

*ANSWERC*REFERENCELesson Plan R02-05-LP-053NAD-02.07, Kewaunee Refueling OperationsNewMemory

*QNUM 022*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL R*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 2.3.2*QUESTIONA point source in containment is reading 300 mRem/hr at a distance of two (2) feet. Twooptions are available to complete a mandatory work assignment near this radiation source:

Option 1 - ONE operator can perform the assignment in fifty (50) minutes working at a distanceof three (3) feet from the source.

Option 2 - THREE operators, using special extension tooling, can perform the assignment insixty (60) minutes at a distance of six (6) feet from the source

Which is the preferred option based on ALARA and the corresponding total exposure?

a. Option 1, with a total exposure of 0.100 Person-REM

b. Option 1, with a total exposure of 0.111 Person-REM

c. Option 2, with a total exposure of 0.100 Person-REM

d. Option 2, with a total exposure of 0.111 Person-REM*ANSWERC*REFERENCEINPO EXAM BANK, 12/11/2000 Kewaunee ExamModifiedHigher

*QNUM 023*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL R*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 2.4.1*QUESTIONWhich of the following is listed in E-0, “Reactor Trip or Safety Injection”, step 1 CONTINGENCYACTIONS but is NOT in FR-S.1, “Response to a Nuclear Power Generation/ATWS”, step 1CONTINGENCY ACTIONS?

a. Source range counts

b. Intermediate range power

c. Reactor Trip Breakers

d. Bypass Breakers*ANSWERB*REFERENCEFR-S.1, “Response to a Nuclear Power Generation/ATWS”E-0, “Reactor Trip or Safety Injection”NewHigher

*QNUM 024*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL R*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 2.4.7*QUESTIONWhich of the following is the basis for maintaining SG Narrow Range levels between 4% and50% during procedure ECA-0.0, "LOSS OF ALL AC POWER"?

a. Ensures the capability to cooldown the reactor only after AC power is restored.

b. Ensures heat transfer capability exists to remove heat from the RCS.

c. Narrow Range level is the only reliable indication of SG inventory available aftera loss of all AC power.

d. Provides capability to monitor the SGs for a Steam Generator Tube Rupture.*ANSWERB*REFERENCEINPO Exam Bank - Byron Exam 10/20/2000ECA-0.0, "LOSS OF ALL AC POWER" and Background DocumentNewHigher

*QNUM 025*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL R*EXMNR K Walton*QVAL 1.00*SEC*SUBSORT*KA W/E11EK32*QUESTIONWhich ONE of the following describes the mitigating strategies contained in ECA-1.1, “Loss ofEmergency Coolant Recirculation?”

A. Minimizing the depletion of the RWST, Maximizing Subcooling, determination ofminimum containment spray requirements.

B. Maximizing Subcooling, minimizing the depletion of the RWST, anddepressurization of the RCS to minimize break flow.

C. Minimizing the depletion of the RWST, determination of minimum containmentspray requirements, and depressurization of the RCS to minimize break flow.

D. Maximizing subcooling, determination of minimum containment spray, anddepressurization of the RCS to minimize break flow.

*ANSWERC*REFERENCEFR-C.2, “Response to Degraded Core Cooling" and Background DocumentBankMemory

*QNUM 026*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 001000K103*QUESTIONGiven the following CRDM coil rod motion sequence:

- 1. Stationary Gripper Energized at Low Voltage- 2. Stationary Gripper Energizes at High Voltage- 3. Movable Gripper Energizes- 4. Stationary Gripper De-energizes

The next step in the sequence is __________ and the rod is being moved ____________

a. Lift Coil De-energizes, Inward

b. Lift Coil Energizes, Outward

c. Stationary Gripper Energizes at Low Voltage, Inward

d. Stationary Gripper Energizes at High Voltage, Outward*ANSWERB*REFERENCELesson Plan RO2-05-LP049, Rod Control and RPISD-49, Section 3.3.2NewHigher

*QNUM 027*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR K. Walton*QVAL 1.00*SEC*SUBSORT*KA 001000K611*QUESTIONWith the plant in the operating mode, the reactor operator receives ROD CONTROL SYSTEMABNORMAL annunciator and SER point 1692, “Rod Control System Non-Urgent Failure.” Instrument and Control technicians narrow the problem to the Rod Control Logic Cabinet. Whatmay have caused this condition to occur?

a. Slave cycler cycles without a GO pulse

b. A redundant power supply has been lost

c. Oscillator fails to generate signals when called for

d. There is a loose printed circuit card in the logic circuitry*ANSWERB*REFERENCERO2-05-LP049 Lesson Plan, Rod Control and RPI, pg 43 & 44 of 59.Annunciator 47043-R, Rod Control System Abnormal NewMemory

*QNUM 028*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 013000K403*QUESTIONWhich of the following conditions results in a Main Steam Isolation?

a. Containment pressure of 15 psig.

b. Steamline flow of 4E6 lb/hr AND an "SI" signal.

c. Steamline flow of 5E6 lb/hr AND Tavg of 530 deg F.

d. Steamline flow of 0.8E6 lb/hr, Tavg of 530 deg F, AND an "SI" signal.*ANSWERD*REFERENCEKNPP System Description 55, Engineered Safety FeaturesBankMemory

*QNUM 029*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 004000K305*QUESTIONThe unit is at 100% power with Charging pump A operating in automatic. Charging Line FlowControl valve, CVC-7, is throttled to 70%. CVC-7 then fails open. Charging pump A’s speedwill ....

a. NOT change during this event

b. decrease at first, then returns to its initial speed

c. increases at first, then remains above its initial speed

d. decreases at first, then remains below its initial speed*ANSWERA*REFERENCELesson Plan RO2-05-035, CVCSSystem Description 35, CVCSNewHigher

*QNUM 030*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 015000K603*QUESTIONA plant startup is in progress with power at 8 percent. Intermediate Range drawer N-36 LevelTrip switch is in the BYPASS position. What is the plant response to removal of N-36 controlpower fuses and the reason for the plant response?

a. A trip will occur because the Level Trip Switch bypass function will be removed.

b. A trip will not occur because the Level Trip Switch is in the bypass position andthe bypass function is not affected at any power level.

c. A trip will not occur because the Level Trip Switch is in the bypass position andpower is less than P-10.

d. A trip will occur because the Level Trip Switch bypass function is operable onlyabove P-10.

*ANSWERA*REFERENCELesson Plan RO2-05-048, NISSystem Description 48, NISNRC EXAM 11/13/1990 Millstone 3BankHigher

*QNUM 031*HNUM*ANUM*QCHANGED FALSE*ACHANGED FALSE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C. Zoia*QVAL 1.00*SEC*SUBSORT*KA 017000A401*QUESTION

While operating at 100% power, Graphics Display 4 on PPCS shows the B7 CET temperature tobe 592°F.

Which of the following sequence of actions identifies how the operator would display the B7 CETtemperature value (Channel 20 on Train B) at the ICCMS panels?

Depress the CET ID/CET TEMP pushbutton to illuminate the...

A. CET TEMP lamp, then depress the AVG/HOT pushbutton to display the B7 CET temperature.

B. CET TEMP lamp, then depress the REF1/REF2 pushbutton to display the B7 CET temperature.

C. CET ID lamp, then depress the REF1/REF2 pushbutton until “B7" is displayed, then depress the CET ID/CET TEMP again to display the B7 CET temperature.

D. CET ID lamp, then depress the AVG/HOT pushbutton until “20" is displayed, then depress the CET ID/CET TEMP again to display the B7 CET temperature.

*ANSWERD

*REFERENCESystem Description 50, Incore Instrumentation & Inadequate Core Cooling MonitorSections 1.4, CET Operation and 3.4.3, CET Instrumentation NewMemory

*QNUM 032*HNUM*ANUM*QCHANGED FALSE*ACHANGED FALSE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 022000A301*QUESTIONGiven the following conditions:

- Four CFCUs were running prior to the event- A Safety Injection signal was just received- Containment Pressure has increased to 3.5 psig and is currently stable

What condition would you expect the CFCUs to be in at this time?

a. All CFCUs would be running with SW return isolation valves throttled to maintaintemperature

b. All CFCUs would be running with CFCU Emergency Discharge dampers open andSW return isolation valves throttled to maintain temperature

c. All CFCUs would be running with SW return isolation valves fully open

d. All CFCUs would be running with CFCU Emergency Discharge dampers and SWreturn isolation valves fully open

*ANSWERC*REFERENCESystem Description 18, Reactor Building Ventilation (RBV) & Hydrogen ControlLesson Plan RO2-04-LP 18, Reactor Building Ventilation SystemNewHigher

*QNUM 033*HNUM*ANUM*QCHANGED FALSE*ACHANGED FALSE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 076000K307*QUESTIONGiven the following conditions:

- The plant has tripped and a Safety Injection signal has been generated.- Engineered Safeguard Features Actuation System Train A relays have failed to

operate ONLY the Service Water System valves.- Train B relays have operated properly.

At the completion of the SI sequence, what is the status of Service Water flow to ComponentCooling Water (CCW) Heat Exchanger ‘A’, if NO operator action is taken?

a. There will be NO Service Water flow through the CCW heat exchanger.

b. SW flow will be at a set constant value lower than its post-accident expected value.

c. SW flow through the CCW heat exchanger will be at its post-accident expectedvalue.

d. SW flow will be lower than its post-accident expected value and controlled by theCCW outlet header temperature.

*ANSWERD*REFERENCESystem Description 2, Service WaterKewaunee Exam BankBankHigher

*QNUM 034*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 059000 2.2.2*QUESTIONGiven the following conditions:

- The plant is at 55% power and steady.- The “A” Main FW pump is in pullout.- The “B” Main FW pump is running with two condensate pumps.- Annunciator 47062-A, “S/G A Program Level Deviation” is LIT.- All 3 S/G A level indicators are 38% and steady.

Which of the following describes actions to be taken by the operator based on these conditions?

a START “A” Main FW pump per N-FW-05B, Feedwater System Normal OperationAND MONITOR “A” S/G level automatic control for proper operation.

b. REDUCE load to < 50% AND MONITOR “A” S/G level automatic control for properoperation.

c. Place Feedwater Flow Control Valve FW-7A to MANUAL AND GO to A-MI-87,Bistable Tripping for Failed Reactor Protection or Safeguards Instrumentation.

d. GO to A-FW-05A, Abnormal Feedwater System Operation, AND DETERMINE ifmanual feedwater control is required.

*ANSWERD*REFERENCEA-FW-05A, Abnormal Feedwater System Operation, step 4.4NewHigher

*QNUM 035*HNUM*ANUM*QCHANGED TRUE*ACHANGED FALSE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 003000K201*QUESTIONGiven the following plant conditions:

- The reactor is at 100% power- All systems are in a normal lineup

Based on these conditions, which one of the following correctly states the power supply tothe Reactor Coolant Pumps?

RXCP A RXCP B

a. MAT MAT

b. RAT MAT

c. MAT RAT

d. RAT RAT*ANSWERA*REFERENCESKNPP SD 39, 4160 V SystemKNPP SD 36, RCSNewMemory

*QNUM 036*HNUM*ANUM*QCHANGED FALSE*ACHANGED FALSE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA W/E08EA202*QUESTIONIn procedure FR-P.1, Response to Imminent Pressurized Thermal Shock Condition, thestep to check if SI can be terminated is based on which of the following parameter(s):

a. RCS Subcooling ONLY.

b. RCS Subcooling and RCS Cold Leg Temperatures.

c. RCS Pressure ONLY.

d. RCS Pressure and RCS Cold Leg Temperatures.*ANSWER A*REFERENCEIPEOP Background Document for FR-P.1Lesson Plan RO4-04-LP-016, Response to Imminent Pressurized Thermal Shock ConditionNewMemory

*QNUM 037*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA W/E12EA13*QUESTIONECA-2.1, Uncontrolled Depressurization of Both Steam Generators, has been entered fromE-2, Faulted Steam Generator Isolation. Containment pressure is 1.0 psig. Each steamgenerator is being fed at 100 gpm producing an RCS cooldown rate of 120 degrees F/hr.Steam generator water levels are as follows:

Steam Generator A narrow range levels - 2%Steam Generator B narrow range levels - 8%

Based on the conditions above, what is the appropriate initial operator action?

a. Decrease feed flow to each steam generator to 60 gpm.

b. Decrease feed flow to “A” steam generator ONLY to 60 gpm.

c. Increase feed flow as required to maintain “A” steam generator narrowrange level greater than or equal to 4%.

d. Control feed flow as required to maintain RCS hot leg temperatures stableor decreasing.

*ANSWERA*REFERENCEECA-2.1, Uncontrolled Depressurization of Both Steam GeneratorsNewHigher

*QNUM 038*HNUM*ANUM*QCHANGED FALSE*ACHANGED FALSE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 000026K303*QUESTIONThe following plant conditions exist:

- A safety injection has actuated- A transition has been made to ES-1.1, SI Termination- No charging pump is running- CC flow to the RXCP thermal barrier HX has been lost since the SI actuation

What action is initially taken associated with RXCP seal cooling and what is the reason forthe action?

a. RXCP seal injection is isolated before starting a charging pump, to avoidtaking time to reestablish seal cooling since RXCP seals are already heatedup.

b. A charging pump is started and then CC flow is established to the RXCPthermal barriers, to prevent steam binding of the CC system.

c. CC flow is established to the RXCP thermal barriers and then a chargingpump is started, to prevent RXCP shaft warping.

d. CC flow is established to the RXCP thermal barriers, to prevent thermalshock to the RXCP seals.

*ANSWERA*REFERENCEES-1.1, SI Termination and Background DocumentLesson Plan RO4-04-LP-005NewMemory

*QNUM 039*HNUM*ANUM*QCHANGED FALSE*ACHANGED FALSE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA W/E10 2.4.4*QUESTIONGiven the following plant conditions:

- Reactor trip occurred with subsequent loss of RXCPs.- RCS Pressure is 800 psig- Operators have implemented ES-0.2, "Natural Circulation Cooldown" to

go to Cold Shutdown.- A cooldown rate of 25 deg F/hour has been established.- RCS depressurization has been initiated- PZR level - Unexpected large variations are occurring- RVLIS RXCPs OFF Indication - 90%

The Shift Manager has determined that cooldown and depressurization shall proceed asquickly as possible. Which ONE of the following describes the appropriate actions?

a. Pressurize the RCS to collapse the voids, continue the cooldown andremain in ES-0.2, Natural Circulation Cooldown.

b. Raise the cooldown rate to collapse the voids and remain in ES-0.2,Natural Circulation Cooldown.

c. Pressurize the RCS to collapse the voids, continue the cooldown andtransition to ES-0.3, "Natural Circulation Cooldown With Steam Voids inVessel”.

d. Raise the cooldown rate to collapse the voids and transition to ES-0.3,"Natural Circulation Cooldown With Steam Voids in Vessel.

*ANSWERC*REFERENCEModifiedHigher

*QNUM 040*HNUM*ANUM*QCHANGED FALSE*ACHANGED FALSE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 000005K105*QUESTIONGiven the following plant conditions:

- The unit is at 80% power. - Control Bank D rod K7 is stuck at 220 steps (not the most reactive rod). - All other Control Bank "D" rods are at 220 steps. - Tavg = 567°F.

How would the shutdown margin calculation performed prior to the condition discoveredabove be affected?

a. No effect on shutdown margin.

b. Shutdown margin would be more conservative.

c. Shutdown margin would be less conservative.

d. The effect on shutdown margin can not be determined.*ANSWERC*REFERENCESystem Description 49 - Rod Control and RPITechnical SpecificationsNewHigher

*QNUM 041*HNUM*ANUM*QCHANGED FALSE*ACHANGED FALSE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C. Zoia*QVAL 1.00*SEC*SUBSORT*KA 000015A109*QUESTIONWhich of the following indications will be inaccurate during the performance of ES-0.2,"Natural Circulation Cooldown", with RXCPs secured?

a. RCS core exit TCs.

b. RCS wide range hot leg temperature.

c. RCS T-average indication.

d. RCS wide range cold leg temperature.*ANSWERC*REFERENCEES-0.2, Rev 0, Caution before step 1, p 2.NRC Exam Bank - Point Beach 1 & 2 04/29/1991BankMemory

*QNUM 042*HNUM*ANUM*QCHANGED FALSE*ACHANGED FALSE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 000024K102*QUESTIONThe following plant conditions exist:

- Reactor power is 80%- Rod Control is in MANUAL- All other controls are in AUTO

An inadvertent Emergency Boration was performed for two minutes.Considering steady-state to steady-state conditions, which of the following parameterswill NOT change?

a. Reactor Power

b. RCS Tavg

c. Przr Level

d. S/G Pressure*ANSWERA*REFERENCEPWR FundamentalsINPO Exam Bank - Braidwood 4/1/1996 ExamBankMemory

*QNUM 043*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 056000A204*QUESTIONGiven the following conditions:

- The plant is at 50% power- Condensate pump A is in pullout- Condensate pump B is running

If condenser hot well level subsequently decreases to 10%, which one of the actionsbelow is now required?

a. Startup condensate pump A per N-CD-03, Condensate System.

b. Address abnormal condensate conditions per A-CD-03, CondensateSystem Abnormal Operation.

c. OPEN MU-3B, Condenser Emergency Make-up valve per N-CD-03,Condensate System.

d. Respond to the reactor trip per E-0, Reactor Trip or Safety Injection*ANSWERD*REFERENCELesson Plan RO2-02-LP-003, Condensate and Air Removal SystemNewHigher

*QNUM 044*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 000051 2.1.30*QUESTIONDue to decreasing condenser vacuum, the operator performs the actions of E-AR-09,Loss of Condenser Vacuum. At one point, condenser pressure increases to 5 inches Hgabsolute, and the operator must locally place the hogging jet in service.

In addition to opening MS-400, Steam Supply to Hogging Jet, and throttling MS-401,Steam to Hogging Jet, to maintain between 105-115 psig on PI-11323, four additionalvalves, listed below, must be aligned to place the hogging jet in service:

- AR-302, Gland Steam Cdsr Exhaust to Outside- AR-305, Gland Steam Cdsr Exhaust to Vent- AR-100, Hogging Jet Air Inlet- AR-2A, First Stage Ejector Inlet

Which of the following is the correct valve alignment?

AR-302 AR-305 AR-100 AR-2A

a. CLOSED OPEN CLOSED OPEN

b. OPEN CLOSED OPEN CLOSED

c. CLOSED OPEN OPEN CLOSED

d. OPEN CLOSED CLOSED OPEN*ANSWERB*REFERENCEKNPP Lesson Plans RO2-02-LP-003.004 and O-AOP-LP-D8E-AR-09, Loss of Condenser VacuumNewHigher

*QNUM 045*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 071000A302*QUESTIONThe Gaseous Radioactive Waste System (WG) vent header pressure has just increasedto 2 psig. Per A-GWP-32B, the AUTOMATIC ACTIONS the operator must now verify are:

a. The start of the Waste Gas Compressors.

b. The closure of Gas Decay Tank inlet isolation valves for the tank selectedfor fill.

c. The closure of Gas Decay Tanks to Holdup Tanks valve.

d. The opening of Gas Decay Tank inlet isolation valve for the tank selectedfor standby.

*ANSWERA*REFERENCEKNPP System Description 32B, Gaseous Radioactive Waste Disposal (GWP)NewMemory

*QNUM 046*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 071000A409*QUESTIONThe contents of a Gas Decay Tank is being released in accordance with the appropriateadministrative controls when Gas Decay Tanks to Plant Vent, WG-36/CV-31215, closed.Which of the following monitors could have caused this to occur?

a. BOTH R-13 and R-14 (Aux Building Vent Monitors)

b. BOTH Aux. Area Monitors 03-06 and 03-08 (Beta Air Monitors Aux.Building)

c. ONLY R-13 (Aux Building Vent Monitor)

d. ONLY R-14 (Aux Building Vent Monitor)*ANSWERA*REFERENCEKNPP System Description 32B, Gaseous Radioactive Waste Disposal (GWP)KNPP System Description 45, Radiation Monitoring (RM)NewMemory

*QNUM 047*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 072000K501*QUESTIONWhich of the following describes the detector types used in Area Radiation Monitors atKewaunee?

a. ONLY GM tubes and ion chambers

b. ONLY ion chambers

c. ONLY GM tubes

d. Ion chambers, GM tubes AND scintillation detectors*ANSWERA*REFERENCEKNPP System Description 45, Radiation Monitoring (RM)RO2-01-LP045, Radiation MonitoringNewMemory

*QNUM 048*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 072000 2.3.10*QUESTIONProcedure A-RM-45, Abnormal Radiation Monitoring, requires the operator to determineif Post Accident Recirc must be started due to a failure of R-23, Control Room VentMonitor, by monitoring specific process and area monitors for increasing radiation levels.

Besides R-1, Control Room Area Monitor, what additional AREA Radiation monitor(s), ifany, must be monitored and Post Accident Recirc manually started on increasing levelsof radiation?

a. BOTH R-10, New Fuel Pit Area Monitor AND R-5, Fuel Handling AreaMonitor.

b. NO additional Area Radiation Monitors.

c. ONLY R-10, New Fuel Pit Area Monitor.

d. ONLY R-5, Fuel Handling Area Monitor.*ANSWERD*REFERENCEKNPP System Description 45, Radiation Monitoring (RM)A-RM-45, Abnormal Radiation MonitoringNewMemory

*QNUM 049*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 002000A203*QUESTIONES-0.2, Natural Circulation Cooldown, is being implemented. The following conditionsexist:

- RCS cold leg Temp is at 380 deg F.- RCS Pressure is at 1450 psig.- All CRDM fans are off and CANNOT be started.- 18 hour waiting period has begun.

What is the basis for the 18 hour waiting period?

a. Prevent damage to the CRDM coils due to overheating.

b. Ensure heat is being removed from the Steam Generator to prevent voidformation in the U-tubes.

c. Minimize void formations in the Reactor Vessel head during subsequentRCS depressurization to place RHR in service.

d. Allow sufficient flow to the upper head region to make the upper head fluidtemperature equal to the cold leg fluid temperature.

*ANSWERC*REFERENCEES-0.2, Natural Circulation CooldownES-0.2 Background DocumentBankMemory

*QNUM 050*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 010000K103*QUESTIONThe following plant conditions exist:

- PZR pressure control channel selector switch is in the 4-3 position- PZR pressure yellow channel (PT-449 IV) has just failed low

What is the effect of these conditions on the RCS?

a. All PZR heaters will come ON; PZR PORVs PR-2A and PR-2B would notbe available to open on a subsequent high RCS pressure condition.

b. PZR heaters are unaffected; ONLY PZR PORV PR-2A would not beavailable to open on a subsequent high RCS pressure condition.

c. All PZR heaters will come ON; PZR PORV PR-2A would not be availableto open on a subsequent high RCS pressure condition.

d. PZR heaters are unaffected; PZR PORVs PR-2A and PR-2B would not beavailable to open on a subsequent high RCS pressure condition.

*ANSWERD*REFERENCERO2-05-LP-36C, Pressurizer Pressure ControlNewHigher

*QNUM 051*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 012000K304*QUESTIONFollowing an ATWS and an SI actuation from 100% power, the Reactor Trip Breakersremain closed. What effect will this have on the plant?

a. Automatic Turbine Trip will not occur.

b. Automatic steam line isolation will be blocked.

c. Automatic SI reactuation CANNOT be blocked.

d. Feedwater isolation due to SI actuation will be blocked.*ANSWERC*REFERENCERO2-05-LP472, Reactor Protection - Day 2NewHigher

*QNUM 052*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 000055K101*QUESTIONWhich of the following parameters is monitored to determine the need to minimize DCloads while performing ECA-0.0, LOSS OF ALL AC POWER?

a. Battery amps

b. Battery amp-hours

c. Battery volts

d. Battery specific gravity*ANSWERC*REFERENCEKNPP Lesson Plan RO4-04-LP040, Loss of all AC PowerComanche Peak NRC Exam 11/26/1990ECA-0.0, Loss of all AC PowerBankMemory

*QNUM 053*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 000057A102*QUESTIONGiven the following:

- The unit is stable at 15% power.- A failure of Instrument Bus I, BRA-113, occurs.- All systems and control loops are in their NORMAL position.

Which of the following action(s) are required, if any, to restore pressurizer (PRZR)pressure and level conditions resulting from this failure?

a. Place PRZR spray valves in MANUAL, Position PRZR Pressure Control Switch to another position, AND Then place PRZR spray valves back in AUTO.

b. Place Charging Pump Speed control to MANUAL, Position PRZR Level Control Switch to another position, AND Then place Charging Pump Speed control back to AUTO.

c. Position PRZR Level Control Switch to another position, AND Then restore normal letdown and PRZR heaters.

d. No actions are required to restore PRZR pressure and level.*ANSWERD*REFERENCEKewaunee Lesson Plan RO2-05-36C, “Pressurizer Pressure Control”Kewaunee System Description 36, “Reactor Coolant System”A-MI-87, Bistable Tripping for Failed Reactor Protection or Safeguards Inst.NewHigher

*QNUM 054*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 014000K502*QUESTIONWhich one of the following would cause annunciator 47041-P, ROD BOTTOM RODDROP, to alarm?

a. Control Bank B demand is 38 and a Control Bank B IRPI reads 18.

b. Control Bank A demand is 18 and a Control Bank A IRPI reads 32.

c. Shutdown Bank B demand is 32 and a Shutdown Bank B IRPI reads 18.

d. Shutdown Bank A demand is 18 and a Shutdown Bank A IRPI reads 32.*ANSWERC*REFERENCEKNPP System Description 49, Rod Control and RPIKewaunee Exam Bank RO2-05-LP049.004 010KNPP Lesson Plan RO2-05-LP049, Rod Control and RPIBankHigher

This Question was dropped from the exam after it was administered because all fourchoices are correct.

*QNUM 055*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 016000K401*QUESTIONGiven the following:

- There has been a fire necessitating the evacuation of the control room.- E-0-06, Fire in Alternate Fire Zone has been entered from E-FP-08,

Emergency Operating Procedure - Fire.

Which of the following indications is available at the Dedicated Shutdown Panel?

a. S/G 1A Narrow Range Level

b. Charging Flow

c. RWST Level

d. Reactor Coolant Loop B Hot Leg Temp*ANSWERC*REFERENCEKNPP Fire Protection Program Plan, Appendix DE-0-06, Fire in Alternate Fire ZoneE-FP-08, Emergency Operating Procedure - Fire.NewMemory

*QNUM 056*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 026000A301*QUESTIONGiven the following conditions:

- A large break LOCA occurs.- Containment pressure is observed to be 25 psig.- Containment Spray has NOT initiated.- Manual actuation of Containment Spray has been unsuccessful.- All other ESF actuations and components have functioned normally.

What actions need to be taken to manually initiate Containment Spray for Train A?

Manual start of ICS Pump A and ...(1) ICS-5A/MV-32066 and ICS-6A/MV32067, Ctmt Spray Pump ADischarge Isolation valves(2) ICS-201/CV-31272 and ICS-202/CV31273, ICS Recirculation RWSTvalves(3) CI-1001A/CV31393 and CI-1001B/CV-31394, Caustic Additive to CtmtSpray valves

a. (1) check auto open (2) check closed (3) check auto open

b. (1) manual open (2) check closed (3) check auto open

c. (1) manual open (2) check closed (3) manual open

d. (1) manual open (2) manual close (3) manual open*ANSWERC*REFERENCEFR-Z.1, Response to High Containment Pressure, Step 3, pages 3-4CS Integrated Logic Diagram E-1604, Rev. USystem Integrated Logic Diagram ICS E-2012, Rev. KBankMemory

*QNUM 057*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 029000A102*QUESTION

Given the following conditions:- Radiation Monitor R-11, Containment Atmosphere, is in HIGH alarm.- All other plant conditions are normal

Which of the following lists valves in the Reactor Building Ventilation System to be verifiedautomatically CLOSED by the operator?

a. ONLY the following valves:- TAV-12, Cntmt Purge/Vent Supply- RBV-2, Cntmt Purge/Vent Supply B- RBV-5, Cntmt Purge/Vent Exhaust- RBV-3, Cntmt Purge/Vent Exhaust B- SA-7003B, Hydrogen Dilution to Cnmt- LOCA-2B, Post LOCA H2 Cntmt Vent Isol B.

b. ONLY the following valves:- TAV-12, Cntmt Purge/Vent Supply- RBV-5, Cntmt Purge/Vent Exhaust- SA-7003B, Hydrogen Dilution to Cnmt- LOCA-2B, Post LOCA H2 Cntmt Vent Isol B.

c. ONLY the following valves:- TAV-12, Cntmt Purge/Vent Supply- RBV-2, Cntmt Purge/Vent Supply B- RBV-5, Cntmt Purge/Vent Exhaust- RBV-3, Cntmt Purge/Vent Exhaust B.

d. ONLY the following valves- RBV-2, Cntmt Purge/Vent Supply B- RBV-3, Cntmt Purge/Vent Exhaust B- SA-7003B, Hydrogen Dilution to Cnmt- LOCA-2B, Post LOCA H2 Cntmt Vent Isol B.

*ANSWERA*REFERENCEA-RM-45, Abnormal Radiation Monitoring SystemNewMemory

*QNUM 058*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 103000A101*QUESTIONECA-1.1, Loss of Emergency Coolant Recirculation, determines the required number ofoperating ICS pumps based on which of the following?

a. Containment pressure, containment temperature, and sump level.

b. Containment pressure, operating CFCUs, and sump level.

c. Containment temperature, operating CFCUs, and RWST level.

d. Containment pressure, operating CFCUs, and RWST level.*ANSWERD*REFERENCEINPO Exam Bank - Byron Exam 06/29/2000BankMemory

*QNUM 059*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 033000A203*QUESTIONThe plant is at 100% power when control room operators receive SPENT FUEL POOLABNORMAL Annunciator. The SFP level is decreasing AND is lower than the SFP canallevel. The CRS instructs you to initiate makeup to the SFP. Per procedure A-SFP-21,Abnormal SFP Cooling and Cleanup System Operation, you would use. . .

a. the RWST

b. Service Water

c. the Reactor Makeup Control System

d. Reactor Makeup Water through manual makeup valveANSWERB*REFERENCEINPO Exam Bank - Kewaunee Exam 02/24/1997ModifiedMemory

*QNUM 060*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 035000A301*QUESTIONThe Unit is at 40% power in a power ascension to full power. All systems are aligned intheir normal lineups for the current power level except Turbine EHC control is inMANUAL-IMP OUT. The operator depresses the CV raise pushbutton for 2 seconds tocontinue the load ascension. Which of the following is the response of the main feedwaterregulating valves to this action?

The Main Feedwater Regulating Valves will initially throttle...

a. CLOSED due to swell, and then throttle OPEN when level drops below44%.

b. OPEN due to the steam flow/feed flow mismatch, and then regulate tocontrol level at 44%

c. CLOSED due to the steam flow/feed flow mismatch, and then throttleOPEN when level drops below 44%.

d. OPEN due to shrink, and then regulate to control level at 44%.*ANSWERB*REFERENCEINPO Exam Bank - Beaver Valley 2 Exam 03/17/1997ModifiedHigher

*QNUM 061*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 039000A404*QUESTIONSP-05B-284, “Turbine Driven AFW Pump Full Flow Test - IST,” was in progress. Theturbine driven auxiliary feedwater pump (TDAFP) was started and had been running for2 minutes.

Alarm window 47062-N, “T/D AFW Pump Abnormal” then annunciates and the NAOreports the TDAFP auxiliary lube oil pump is continuously stopping and starting with lubeoil pressure fluctuating between 8 and 17 psig.

Which ONE of the following correctly explains the above conditions?

a. Conditions are normal, no operator action is required, the test shouldcontinue.

b. Conditions are normal, the NAO should be directed to locally shutdown theauxiliary lube oil pump, the test should continue.

c. The shaft driven pump has malfunctioned, the test should be terminated.

d. The Auxiliary Lube Oil Pump has malfunctioned, the test should beterminated.

*ANSWERC*REFERENCEKNPP System Description 05B, Auxiliary Feedwater System; ARP 47062-NBankHigher

*QNUM 062*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 055000K106*QUESTIONGiven the following conditions:

- The plant is at 100% power- S/G blowdown is in service in Mode II- Condenser air removal is aligned for normal operation- The NCO positions the R-19 keyswitch to the OFF position

Which of the following describes the effect of the operator actions?

a. Blowdown flowpath switches to Mode I alignment.

b. Blowdown flowpath switches to the Primary Sampling System.

c. Condenser Air Ejector discharge AR-6 (CV-31168) remains in the ductposition.

d. Condenser Air Ejector discharge AR-6 (CV-31168) switches to its ATMposition.

*ANSWERC*REFERENCEINPO Exam Bank - Kewaunee 12/11/2000 NRC ExamKNPP System Description 09, Air Removal System (AR)BankHigher

*QNUM 063*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C. Zoia*QVAL 1.00*SEC*SUBSORT*KA 068000A204*QUESTIONDuring a liquid radwaste discharge from the Waste Condensate Tanks to the Auxiliarybuilding standpipe, control room operators receive a Waste Disposal Panel Trouble Alarmand dispatch an operator. The operator reports from the Waste Disposal Panel (53702)that “LIQUID WASTE MONITOR R-18 HIGH RADIATION" has alarmed. RadiationMonitor R-18 is verified to be alarming, but automatic action(s) do NOT occur. Whatautomatic operation of A-RM-45, Abnormal Radiation Monitoring System must now beperformed manually?

a. Manually close WD-19, Waste Liquid Discharge Isolation Valve .

b. Manually close WD-17, Waste Condensate Pumps Discharge Valve.

c. Manually close WD-22, Waste Condensate Pumps to Auxiliary BuildingStandpipe.

d. Stop Waste Condensate Pump 1A.

*ANSWERA*REFERENCEA-RM-45, Abnormal Radiation Monitoring SystemLesson Plan Objective RO2-01-LP045.004Dwg XK-100-131, Flow Diagram Waste Disposal SystemNewMemory

*QNUM 064*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR K Walton*QVAL 1.00*SEC*SUBSORT*KA 005000K101*QUESTIONWhen the RHR system is placed in the shutdown cooling mode of operation, componentcooling is __(1)__ aligned to the associated RHR heat exchanger prior to RHR pump startAND component cooling flows through the __(2)__ side of the RHR heat exchanger.

(1) (2)

a. Automatically Tube

b. Manually Tube

c. Automatically Shell

d. Manually Shell*ANSWERD*REFERENCESystem Description, RHR pg 16Drawings OPERXK-100-18 & 19NewMemory

*QNUM 065*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR K Walton*QVAL 1.00*SEC*SUBSORT*KA 028000K502*QUESTIONA LOCA has occurred. Post-LOCA containment hydrogen concentration is 7%. Whatmethod is available to address hydrogen control in the containment?

a. dilute the containment atmosphere.

b. place the Hydrogen Recombiner in service.

c. vent containment through the Shield Building Ventilation System.

d. spray containment using the containment spray pumps.*ANSWERA*REFERENCEN-RBV-18C, “POST-LOCA Hydrogen Control”NewMemory

This question was dropped from the exam after it was administered because all fourchoices are incorrect.

*QNUM 066*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR K Walton*QVAL 1.00*SEC*SUBSORT*KA 034000A201*QUESTIONDuring refueling operations, an irradiated fuel assembly is dropped in the reactor vessel.A fuel handler reports to the control room that gas bubbles are emanating from thedropped assembly. Shortly afterwards, R-11 alarms on high radiation. The control roomoperator enters E-FH-53A, “Dropped or Damaged Fuel Assembly” procedure and____(1)_____. Controls for the R11 alarm ____(2)_____.

a. (1) verifies that the Auxiliary Building Special Vent system starts(2) automatically stops upward movement of the manipulator hoist

b. (1) verifies that the Containment Vent Isolation occurred(2) do NOT affect the fuel handling system

c. (1) actuates the containment evacuation alarm(2) automatically stops movement of the manipulator trolley and bridge

d. (1) orders the affected area evacuated(2) automatically stops upward movement of the manipulator hoist

*ANSWERB*REFERENCEE-RH-53A, “Dropped or Damaged Fuel Assembly,” 8/17/2001System Description - Radiation Monitoring, pgs 12, & 13.System Description - Fuel Handling, pgs 13, 16 & 28.NewHigher

*QNUM 067*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 2.1.10*QUESTIONIn the event that access to an area with radiation levels in excess of 1000 mrem/hourCANNOT be prevented using a locked door, Technical Specification 6.13 requires thearea to be roped off and conspicuously posted.

Which one of the following lists the additional measure that fulfills the requirements ofTechnical Specifications for the entrance to this area?

a. Install an audible alarm.

b. Setup a control point.

c. Install a flashing light.

d. Setup a dose rate indicating device.*ANSWERC*REFERENCELearning Objective R01-01-LPTS4.010Technical Specification 6.1Kewaunee Exam Bank QuestionBankMemory

*QNUM 068*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR K Walton*QVAL 1.00*SEC*SUBSORT*KA 078000K403*QUESTIONAir Compressor A is operating when cooling water to the compressor is inadvertentlyisolated. The air compressor will trip...

a. due to low jacket water pressure.

b. when the limit for oil temperature is exceeded.

c. when the limit for air outlet temperature is exceeded.

d. due to seal leakage resulting in low air discharge pressure.

*ANSWERC*REFERENCEOP A-AS-1, “Abnormal Station and Instrument Air System Operation”System Description #1, Station and Instrument Air, Pg 9 of 23.BankMemory

*QNUM 069*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 062000 2.1.12*QUESTIONGiven the following:

- RCS Average Temperature = 547 deg F.- The reactor is critical at approximately 3% power.- The “B” Diesel Generator is inoperable.- The NORMAL power supply for pressurizer heater control group “A” was

taken out of service to repair a breaker fault.

Which of the following describes the Technical Specification operability and requiredactions for the pressurizer heaters, if any?

a. Technical Specifications requirements are MET and no action is required.

b. Technical Specifications requirements are NOT met, and within 1 houraction is required to go to at least HOT STANDBY within the next 6 hours.

c. Technical Specifications requirements are NOT met, and within 1 houraction is required to go to at least HOT SHUTDOWN within the next 6hours.

d. Technical Specifications requirements are NOT met, and within 1 houraction is required to go to at least COLD SHUTDOWN within the next 36hours.

*ANSWERB*REFERENCEKewaunee Lesson Plan RO2-01-LP-36B, PZR and PRTTech Spec 3.1.a.6 and its basisKewaunee System Description 38, DC & Emergency AC PowerNewHigher

*QNUM 070*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 063000K201*QUESTIONWhich of the following uses Safeguard 125 VDC power as the NORMAL power supply?

a. Bus 4 Circuit Breaker Control

b. 7.5 KVA Inverter BRA-111

c. Reactor Trip Breaker shunt trip coil

d. Non-interruptible Bus BRD-115*ANSWERC*REFERENCESystem Description 38, DC & Emergency AC Electrical DistributionNewMemory

*QNUM 071*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR K. Walton*QVAL 1.00*SEC*SUBSORT*KA 064000K202*QUESTIONPower is lost to BRB-104. Which component(s) associated with the 1B EDG will beaffected by this condition?

A. Field flash circuit AND jacket water pumps ONLY

B. Field flash circuit AND fuel oil priming pump ONLY

C. Jacket water pumps AND immersion heaters ONLY

D. Fuel oil priming pump AND starting air compressors ONLY*ANSWERB*REFERENCEKewaunee System Description 38, DC & Emergency AC PowerKewaunee LP RO2-03-LP-042A, D/GsNewMemory

*QNUM 072*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 073000K301*QUESTIONWhich of the following correctly describes the effect of a failure (HIGH) of R-15, AirEjector Exhaust Monitor during a release?

(1) Air Ejector Discharge Vent. AR-6/CV-31168 positions to DUCT(2) S/G Blowdown Isolation valves CLOSE(3) S/G Sample Isolation valves CLOSE(4) Humidification Steam Inlet CV HS-17-1/CV31770 CLOSES

a. ONLY (1), (2) AND (3) occur

b. ONLY (2) AND (3) occur

c. (1), (2), (3) AND (4) occur

d. ONLY (2), (3) AND (4) occur*ANSWERC*REFERENCEKewaunee System Description 45, Radiation MonitorsA-RM-45, Abnormal Radiation Monitoring SystemE-3748, PRM Integrated Logic DiagramNewMemory

*QNUM 073*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 075000K401*QUESTIONWhich of the following describes the CW condition(s) that would provide an interlock toPREVENT starting a CW pump?

(I) Seal Water Flow < 2 gpm(II) “Forebay Level Low Low” (566' or 42%)(III) Thrust Bearing Cooler Flow < 4 gpm

a. ONLY (II)

b. ONLY (I) and (III)

c. ONLY (II) and (III)

d. (I), (II) and (III)*ANSWERC*REFERENCEKewaunee System Description 4, CW SystemAnnunciator 47051-N, “Forebay Level Low”Lesson Plan RO2-02-LP-004, CW SystemNewMemory

*QNUM 074*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 086000K604*QUESTIONA malfunction of ONE of the “A” Diesel Generator Room CO2 temperature switchesoccurs, causing it to fail HIGH. Which of the following describes the response of the CO2system to the “A” Diesel Generator Room?

a. The CO2 actuation sequence will not begin until a second switch actuationoccurs.

b. The CO2 actuation sequence will sound a local horn, but will notdischarge.

c. The CO2 actuation sequence will sound a local horn and then discharge.

d. The CO2 actuation sequence will start a local, flashing red light, sound alocal horn and then discharge.

*ANSWERC*REFERENCEKewaunee System Description 8, Fire Protection SystemRO2-02-LP-008, Fire Protection SystemNewMemory

*QNUM 075*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 000028A206*QUESTIONGiven the following conditions:

- The plant is at 100% power.- All lineups/switch positions are in their NORMAL position.- Pressurizer Level Channel LT-426 (Channel I) fails LOW

What is the status of the following BEFORE any operator actions are taken?

Letdown Flow Indication “Pressurizer Level Low” Annunciator

a. Normal LIT

b. Normal Not LIT

c. Zero LIT

d. Zero Not Lit*ANSWERA*REFERENCEKewaunee System Description 36, Reactor Coolant SystemAlarm Response 47043-F, PRZR Level LowA-MI-87, Bistable Tripping for Failed RP or Safeguards Inst.NewMemory

*QNUM 076*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA WE13EK11*QUESTIONGiven the following conditions:

- Steam Generator NR Levels are 88%- MSIVs are CLOSED

Per Procedure FR-H.2, “Response to Steam Generator Overpressure”, which of themethods given below has PRIORITY for decreasing S/G pressure?

a. Dump steam using SG PORVs

b. Isolate AFW to the S/Gs

c. Dump steam using Steam Supply to Turbine-Driven AFW Pump

d. Dump steam using Main Steam Isolation Bypass Valves*ANSWERA*REFERENCEKewaunee Lesson Plan RO4-04-LP-036FR-H.2, "Response to S/G Overpressure" and IPEOP Background DocumentNewMemory

*QNUM 077*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 000008A203*QUESTIONIn addressing a PRZR relief valve (PORV) that is stuck open, the associated block valvemust be closed. Which of the following indication(s) can be used to identify which PORVis stuck open?

(I) PR-2A(B) indicating lights on the Mechanical Console C(II) Acoustic monitor indicating lights on the Mechanical Console C(III) Outlet temperatures for each PORV

a. ONLY (I)

b. ONLY (I) OR (III)

c. ONLY (II) OR (III)

d. (I), (II) OR (III)*ANSWERA*REFERENCEKewaunee Lesson Plan RO4-04-LP-36BAnnunciator 47042-A, “Pressurizer PORV Open”Annunciator 47042-B, “Pressurizer PORV Discharge Temperature High”NewHigher

*QNUM 078*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 000009 2.4.45*QUESTIONA LOCA has occurred and a controlled RCS cooldown and depressurization per ES-1.2,“Post LOCA Cooldown and Depressurization” is in progress. ALL ECCS equipment isOPERABLE. RCS Pressure and Temperature is 1500 psig / 480 degrees F. After SIpump A is secured as part of the RCS cooldown and depressurization, the followingalarms occur:

- 47022-D, “CONTAINMENT HIGH PRESSURE SI”- 47024-A, “ACCUMULATOR A PRESSURE HIGH/LOW”- 47024-B, “ACCUMULATOR A LEVEL HIGH/LOW”

What action(s) must be taken, if any, based on these conditions:

a. Trip both RCPs.

b. Restart SI pump A.

c. Trip both RCPs AND Restart SI pump A.

d. No action required.*ANSWERB*REFERENCEES-1.2, “Post LOCA Cooldown and Depressurization”, Step 16a (Contingency Actions).NewHigher

*QNUM 079*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA WE04EK22*QUESTIONWhich of the following systems is considered to be the most likely location for a ruptureor break outside containment, and therefore is the system of primary concern duringECA-1.2, "LOCA Outside Containment"?

a. Safety Injection

b. Residual Heat Removal

c. Component Cooling

d. Chemical and Volume Control*ANSWERB*REFERENCEECA-1.2, LOCA Outside ContainmentIPEOP Background Document for ECA-1.2, LOCA Outside ContainmentINPO Exam Bank - Prairie Island 05/15/2000 ExamKewaunee Lesson Plan RO4-04-LP-020, LOCA Outside ContainmentModifiedMemory

*QNUM 080*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 000029 2.4.49*QUESTIONGiven the following conditions:

- A loss of normal feedwater flow has occurred.- The actions of FR-S.1 "Response to Nuclear Power Generation/ATWS"

must be performed due to a failure of the plant to trip

Which of the following describes the proper sequence of steps to be taken with a failureof the reactor to trip, AFTER beginning to manually insert the Control Rods?

(I) - Locally Open Reactor Trip Breakers(II) - Open Bus 33 and Bus 43 supply breakers(III) - TRIP Rod Drive MG Set Motor & Generator Circuit Breaker Control

Switches

a. (I), (II), and THEN (III).

b. (II), (I), and THEN (III).

c. (II), (III), and THEN (I).

d. (III), (II), and THEN (I).*ANSWERB*REFERENCEFR-S.1 "Response to Nuclear Power Generation/ATWS"IPEOP Background Document for FR-S.1 "Response to Nuclear PowerGeneration/ATWS"NewMemory

*QNUM 081*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 000022A108*QUESTIONGiven the following conditions:

- Reactor power is 100%- VCT level transmitter LT-112 (24015) fails high (100%)

Which of the following describes what occurs if NO operator action is taken?

VCT level decreases __________.

a. because auto makeup capacity is not able to maintain VCT level withletdown diverted

b. with NO auto makeup capability causing charging suction to shift to theRWST

c. until charging pumps lose suction and start to cavitate

d. until auto makeup starts and maintains VCT level*ANSWERC*REFERENCEKewaunee NRC Exam - 10/24/2000Alarm Response 47043-L, “VCT Level High/Low”Kewaunee Lesson System Description 35, CVCSBankMemory

*QNUM 082*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 000025A202*QUESTIONGiven the following conditions:

- The plant is at 255 deg F, cooling down to Cold Shutdown with RHR Train A.- RHR Train B is out of service for testing.- Annunciator 47024-H, CC SURGE TANK LEVEL HIGH/LOW is LIT.- CC Surge Tank Level is 53% and INCREASING.- R-17, Component Cooling Liquid Rad Monitor, is in HIGH ALARM.- VCT level is DECREASING.- All other indications are NORMAL.

Which of the following is the location of the leak?

a. RHR system.

b. SFP heat exchanger.

c. Seal Water heat exchanger.

d. SW system.*ANSWERA*REFERENCEA-CC-31, Abnormal CCW OperationsAlarm Response 47024-H, CC Surge Tank Level High/LowA-RHR-34, Abnormal RHR OperationsA-RM-45, Abnormal Rad Monitoring NewHigher

*QNUM 083*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 000032K101*QUESTIONComplete the following statement:

Source Range neutron detectors operate in the ____(1)_____ region, so decreasing thedetector voltage beyond calibration limits would result in a _____(2)_____ indicated powerlevel.

a. (1) Ionization, (2) higher

b. (1) Proportional, (2) higher

c. (1) Ionization, (2) lower

d. (1) Proportional, (2) lower*ANSWERC*REFERENCEKewaunee Lesson Plan RO2-05-LP048, “Excore Nuclear Instrumentation System”Kewaunee System Description 48, “Excore Nuclear Instrumentation”NewMemory

*QNUM 084*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 000033A201*QUESTIONThe following conditions exist:

- A reactor startup has been completed per N-CRD-49B, “Reactor Startup”.- The Source Range trip is blocked.- The N35 Intermediate Range channel is failed LOW with the level trip bypassed.- The N36 Intermediate Range channel is reading ERRATICALLY.- Source Range counts have just reached 106 CPS

What is the expected indication on the intermediate range nuclear instruments for thiscondition?

a. 10E-3 % Power (IR)

b. 10E-2 % Power (IR)

c. 10E-1 % Power (IR)

d. 10E0 or 1% Power (IR)*ANSWERA*REFERENCEKewaunee Lesson Plan RO2-05-LP048, “Excore Nuclear Instrumentation System”Kewaunee System Description 48, “Excore Nuclear Instrumentation”NewMemory

*QNUM 085*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 000037A113*QUESTIONThe plant is at 100% power. TLA-15, RMS ABOVE NORMAL is in alarm due to increasingradiation level on R-19, S/G Blowdown Liquid Monitor. What action(s) must be taken basedon these conditions?

a. IF the radiation level on R-19, S/G Blowdown Liquid Monitor increases to HIGHalarm, THEN go to E-0-14, “Steam Generator Tube Leak”.

b. Go to E-0-14, “Steam Generator Tube Leak” and perform Operator immediateactions.

c. Go to A-RM-45, “Abnormal Radiation Monitoring System” and verify theautomatic actions occur as listed for R-19, S/G Blowdown Liquid Monitor.

d. Per A-RM-45, “Abnormal Radiation Monitoring System” determine primary-to-secondary leak rate using “R-19 to Leakage Rate Conversion Graph”.

*ANSWERB*REFERENCEA-RM-45, “Abnormal Radiation Monitoring System”E-0-14, “Steam Generator Tube Leak”NewMemory

*QNUM 086*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 000038K308*QUESTIONWhich of the following describes the reason for tripping both RXCPs, if required, per step 1 ofE-3, “Steam Generator Tube Rupture”?

a. To minimize the potential for RCP damage when an RCS depressurization isinitiated.

b. To minimize the heat input when a controlled RCS cooldown is initiated.

c. To prevent the automatic opening of a pressurizer PORV.

d. To prevent unnecessary RCS water depletion.*ANSWERD*REFERENCEBKG E-3, “Steam Generator Tube Rupture” IPEOP Background DocumentProcedure E-3, “Steam Generator Tube Rupture”NewMemory

*QNUM 087*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA WE05EK22*QUESTIONThe following plant conditions exist:

- FR-H.1, Response to Loss of Secondary Heat Sink is in progress.- The CST is unavailable.- Yarway wide range S/G levels are at 20%.- RCS pressure is at 2200 psig.- Containment pressure is 1 psig.

Which of the following heat removal methods is available, if any, before RCS bleed and feedis required AND what is the preferred sequence for establishing flow to at least one S/G?

(1) Depressurize SG and establish Condensate flow(2) Establish AFW flow using Service Water(3) Establish Main Feedwater flow

a. (2), (3), (1)

b. (3), (2), (1)

c. (3), (1), (2)

d. No S/G heat removal method is available; RCS bleed and feed is requiredimmediately.

*ANSWERC*REFERENCEA-FW-05B, Abnormal AFW System OperationFR-H.1, Response to Loss of Secondary Heat SinkBKG FR-H.1, Loss of Secondary Heat Sink IPEOP Background DocumentNewHigher

*QNUM 088*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 000058 2.2.22*QUESTIONWhich of the following places the plant in a 1 hour Limiting Condition of Operation perTechnical Specifications?

a. BRA-101, Station Battery A, fuse blows.

b. BRA-108, Battery Charger A, damaged due to fire.

c. BRA-102, DC DIstribution Train A, damaged bus bar.

d. BRA-111, Instrument Bus 1 Inverter, damaged rectifier.*ANSWERC*REFERENCES :Technical Specifications and BasesA-EDC-38, Abnormal DC Supply and Distribution SystemKewaunee System Description 38, “DC & Emergency AC DistributionLesson Plan RO2-03-LP 038, DC & Emergency AC DistributionNewMemory

*QNUM 089*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 000060K102*QUESTIONThe following plant conditions exist:

- An accidental gaseous release has occurred.- The derived air concentration (DAC) of this release is 4 DAC.

Which of the following is the expected exposure to the whole body of a worker breathing air inthis area for 30 minutes?

a. 2 mrem

b. 5 mrem

c. 8 mrem

d. 10 mrem*ANSWERB*REFERENCE10CFR20, definitions and part 1204Kewaunee System Description 32B, “Gaseous Radioactive Waste Disposal”NewHigher

*QNUM 090*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C. Zoia*QVAL 1.00*SEC*SUBSORT*KA 000061AK302*QUESTIONThe plant is operating at 100% power.

Annunciator 47033-35, TLA-15, RMS ABOVE NORMAL, alarms due to rising count rate on

R-42, S/G A N16 Monitor.

Plant conditions:

• Pressurizer level: 47%, stable.• Pressurizer pressure: 2235 psig.

Which of the following describes the action or actions required for this situation?

A. Enter E-0-14, Steam Generator Tube Leak.

B. Manually trip the reactor and enter E-0, Reactor Trip or Safety Injection.

C. Contact Health Physics to assist in identifying the radiation source.

D. Evacuate the reactor building.

*ANSWERA

*REFERENCEAnnunciator 47033-35, TLA-15, RMS ABOVE NORMAL

NewMemory

*QNUM 091*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA W/E16EK33*QUESTIONGiven the following conditions:

- A LOCA has occurred- The crew is performing a cooldown per ES-1.2 " Post LOCA Cooldown and

Depressurization"- Two Containment Cooling Fan Coil Units are running- Containment pressure is stable at 2.2 psig- A transition to FR-Z.3 "Response to High Containment Radiation Level" is made

on a YELLOW path condition

Why does FR-Z.3 start idle Containment Cooling Fan Coil Units?

a. To remove radioactive particulates during condensation of water vapor.

b. To remove radioactive gases during condensation of water vapor.

c. To support Containment Purge and Vent Subsystem Exhaust filtration.

d. To support Containment Purge and Vent Subsystem Purge filtration.*ANSWERA*REFERENCEFR-Z.3 "Response to High Containment Radiation Level"BKG FR-Z.3 "Response to High Containment Radiation Level" IPEOP Background DocumentINPO Exam Bank - Kewaunee NRC Exam 12/11/2000ModifiedHigher

*QNUM 092*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 000067A217*QUESTIONGiven the following conditions:

- A fire has occurred on site.- E-0-06, “Fire in Alternate Fire Zone” is being implemented.

Complete the following statement:

During implementation of E-0-06, only ____(1)____ equipment is being controlled from theDedicated Shutdown Panel and offsite power is considered to be ____(2)____.

____(1)____ ____(2)____

a. Train A available

b. Train A NOT available

c. Train B available

d. Train B NOT available*ANSWERB*REFERENCEE-0-06, “Fire in Alternate Fire Zone”INPO Exam Bank - Byron NRC Exam 06/29/2000NewHigher

*QNUM 093*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 000069 2.2.23*QUESTIONThe plant was operating at 100% power when the following events occurred:

- 0100: RC-413, Pressurizer Liquid Sampling Isolation valve is determined to beINOPERABLE.

- 0200: RC-412, Pressurizer Liquid Sampling Isolation valve is determined to beINOPERABLE.

What log entry or entries need to be made to track these inoperable valves?

a. An entry for each valve in the Shift Manager’s Log AND in the Shift Manager’sLCO Tracking Log at the time they became INOPERABLE.

b. An entry for each valve in the Control Room Log AND in the Shift Manager’sLCO Tracking Log at the time the valves were discovered to be INOPERABLE.

c. An entry in the Shift Manager’s Log AND the Control Room Log for each valveat the time they became INOPERABLE, AND an entry in the Control Room ShiftTurnover Checklist at shift turnover.

d. One log entry for both valves in the Control Room Shift Turnover Checklist atshift turnover AND an entry for each valve in the Periodic Daily Log at the timeeach valve became INOPERABLE.

*ANSWERC*REFERENCELearning Objective R02-04-LP056.007Technical Specification 3.6.b.3.B, Containment SystemNewMemory

*QNUM 094*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA W/E07EK13*QUESTIONGiven the following:

- A LOCA has occurred.- Containment Pressure is 6 psig.- Core Exit Thermocouples are at 600 deg F.- RCS pressure is 200 psig.- RHR is in its AT-POWER lineup.- FR-C.3, Response to Saturated Core Cooling, is being implemented.

What flows to the RCS must be verified per FR-C.3, Response to Saturated Core Cooling?a. Charging pump flow ONLY.b. RHR and SI pump flows ONLY.c. SI pump flow ONLY.d. Charging and SI pump flows ONLY.

*ANSWERC*REFERENCEFR-C.3, Response to Saturated Core CoolingNewHigher

*QNUM 095*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 000076K305*QUESTIONThe following conditions exist:

- A runback from 80% to 60% power occurred 2 hours ago.- Chemistry samples of the RCS indicate high dose-equivalent I-131.

Why is it desirable to increase letdown flow through the CVC mixed bed demineralizers to 80gpm under these conditions?

a. To reduce RCS activity.

b. To control RCS pH.

c. To reduce RCS corrosion products.

d. To control RCS boron concentration.*ANSWERA*REFERENCEA-RC-36A, High Reactor Coolant ActivityINPO Exam Bank - Kewaunee NRC Exam 12/18/1997BankHigher

*QNUM 096*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 026000 2.4.34*QUESTIONWhile performing ECA-1.1, Loss of Emergency Coolant Recirculation, the “RHR Pump ASupply to ICS Pump A”, valve RHR-400A could not be operated from the control room. Thestep’s contingency action states “Locally open valve”. On which elevation of the auxiliarybuilding is this valve located?

a. 572'

b. 586'

c. 606'

d. 626'*ANSWERB*REFERENCES :Kewaunee System Description 23, ICS SystemDrawings A-204, A-210, OPERXK-100-18 and OPERM-217NewMemory

*QNUM 097*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 029000 2.3.9*QUESTIONIn order to establish a Containment Purge in HOT SHUTDOWN, which of the following isrequired?

1. Notify NRC prior to opening 36" RBV valves.2. Obtain a Gaseous Waste Discharge Permit.3. Verify Annunciator 47051-B, “Containment Vent High Radiation

Disabled” is CLEAR.

a. ONLY 1 and 2.

b. ONLY 1 and 3.

c. ONLY 2 and 3.

d. 1, 2 and 3.*ANSWERC*REFERENCEKewaunee System Description 18, Reactor Building Ventilation SystemAnnunciator 47051-B, Containment Vent High Radiation DisabledN-RBV-18B, Reactor Bldg Vent System Cold Operation and Making ReleasesNewHigher

*QNUM 098*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 000040 2.2.34*QUESTIONFor a Steam Line Break of a given size and location, which of the following initial conditionsresults in the smallest reactivity rate of change immediately after the break?

CORE BURNUP (MWD/MTU) RCS Tavg

a. 9000 450 deg F

b. 9000 547 deg F

c. 5000 450 deg F

d. 5000 547 deg F*ANSWERC*REFERENCEINPO EXAM Bank Kewaunee Exam 12/18/97Reactor Data ManualBankHigher

*QNUM 099*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 2.2.1*QUESTIONGiven the following:

- Reactor power is stabilized at the eight-fold power level.- The Eight-Fold Critical Rod Position is determined to be 65 steps on Control

Bank C.

Which action is required in this situation?

a. Emergency Borate 300 gallons.

b. SHUT DOWN the reactor per N-CRD-49C, “Reactor Shutdown”

c. Get permission from Station Nuclear Engineer to continue with the startup.

d. Verify the Eight-fold Critical Rod Position is within +400pcm of ECP*ANSWERB*REFERENCEN-CRD-49B, “Reactor Startup”N-CRD-49C, “Reactor Shutdown”NewHigher

*QNUM 100*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL B*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 2.1.32*QUESTIONGiven the following:

- The plant is in normal 100% power operations.- Containment Fan Coil Units Emergency Discharge Dampers RBV-150 A and B

both fail OPEN.What is the major concern at this time?

a. Damage to the Nuclear Instrumentation.

b. Damage to the Reactor Vessel Gap.

c. RXCP A motor stator overheating.

d. RXCP B motor stator overheating.*ANSWERD*REFERENCESINPO Exam Bank - Kewaunee Exam 12/11/2000Kewaunee System Description 18, Reactor Building Ventilation System.BankHigher

*QNUM 101*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL S*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 000001K302*QUESTIONGiven the following:

- Reactor Power is 80%.- An unexplained rod withdrawal occurred.- Rods were placed in manual per A-CRD-49, “Abnormal Rod Control Operations”- Tech Spec 3.10.e, Rod Misalignment Limitations, evaluation is being performed

Which of the following identifies the alignment limit and what is the reason for the limit?

a. +12 steps from bank demand to limit core peaking factors.

b. +12 steps from bank demand to assure symmetric power distribution.

c. +24 steps from bank demand to limit the effects of a rod ejection accident.

d. +24 steps from bank demand to assure adequate shutdown margin.*ANSWERD*REFERENCETechnical Specification 3.10.e and basisA-CRD-49, “Abnormal Rod Control Operations”NewHigher

*QNUM 102*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL S*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 000001A203*QUESTIONGiven the following:

- Reactor Power is 90%.- An unexpected rod motion is being addressed per A-CRD-49, “Abnormal Rod

Control Operations”.Which of the following properly describes the initial actions to be taken in the sequence listed?

(1) Check for turbine runback.(2) Check for dropped rod.(3) Position Bank Selector to MANUAL.(4) Dispatch Auxiliary Operator to CRD Equipment Room.

a. (2), (1), (3)b. (1), (3), (2)c. (3), (1), (2), (4)d. (4), (2), (1), (3)

*ANSWERA*REFERENCEA-CRD-49, “Abnormal Rod Control Operations”NewHigher

*QNUM 103*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL S*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 000003 2.1.6*QUESTIONThe plant is operating at 95% power due to rod G7 in control bank C dropping (ratcheting)inwards to position 170 steps. Reactor Engineering just informed you that:

- FQN(Z) exceeds COLR limits by 5%- F HN exceeds COLR limits in the vicinity of the dropped rod.- Axial Flux remains wthin the limits of COLR Figure 7, Axial Flux Difference.

In order to comply with the most stringent Technical Specifications power distribution limits, youorder power reduced to below ....?

a. 90% within 15 minutes.

b. 50% within 1 hour.

c. 90% within 1 hour.

d. 50% within 4 hours.*ANSWERA*REFERENCETechnical Specifications 3.10NewHigher

*QNUM 104*HNUM*ANUM*QCHANGED TRUE*ACHANGED TRUE*QDATE 2004/02/02*FAC 305*RTYP PWR-WEC2*EXLEVEL S*EXMNR C Zoia*QVAL 1.00*SEC*SUBSORT*KA 000011K312*QUESTIONGiven the following:

- A LOCA has occurred from full power operations.- Reactor Coolant System pressure is 140 psig.- Residual Heat Removal injection flow is 0 gpm.- E-1, Loss of Reactor or Secondary Coolant, is in progress at step 18, “Check

If RCS Cooldown and Depressurization is Required”.

Which procedure is appropriate for this plant condition and what is the reason?

a. Stay in E-1, Loss of Reactor or Secondary Coolant, Reactor Coolant System pressure is too low to go to ES-1.2.

b. Stay in E-1, Loss of Reactor or Secondary Coolant, Residual Heat Removal flow will be established in E-1.

c. Go to ES-1.2, Post LOCA Cooldown & Depressurize,Residual Heat Removal flow has NOT been verified in E-1.

d. Go to ES-1.2, Post LOCA Cooldown & DepressurizeReactor Coolant System pressure is too high to cooldown to stay